超臨界水反應器(Supercritical Water-Cooled Reactor, SCWR)為第四代核反應器設計之一，其操作環境高於水的臨界點（374℃、22.1 MPa），具有比輕水式反應器更高的熱轉換效率，大約為45% (現今輕水式反應器熱轉換效率為33%)。相對於現今輕水式反應器，超臨界水反應器的設計簡化且縮小反應槽體積，因而更能有效提升安全性且降低建廠成本。然而，超臨界水具有可無限溶解無極性氣體的特性、高運轉溫度以及高功率密度加劇了輻射水解的效應，使爐心水化學環境之腐蝕性比輕水式反應器來的更加嚴重。因此，發展可適用於超臨界水反應器中高溫、高腐蝕性和高應力爐心環境中的金屬材料，即顯得相當重要。
本論文中，將未經處理之 HR-224鎳基超合金置於模擬超臨界水環境迴路中進行測試，在實驗溫度為700℃、壓力為24.8 MPa和溶氧量為8.3 ppm的環境下，量測腐蝕後質量之改變，並透過電子顯微鏡技術及X-ray繞射分析來探討其腐蝕機制。腐蝕時間(t)在5至500小時以及500至1300小時間，單位面積之質量變化量(∆w/A)分別遵守∆w/A=2.315×〖10〗^(-2) t^0.389 和∆w/A=1.556×〖10〗^(-3) t^0.851之趨勢。腐蝕100到500小時後的試片，從橫截面的分析上發現氧化層為三層結構，由外而內分別為spinel Ni(Cr, Fe)2O4、Cr2O3和不連續Al2O3，在某些區域可發現缺乏氧訊號而鐵與鎳成分比例相當高的顆粒介於Cr2O3和Al2O3之間；在700小時之後，spinel氧化層厚度大幅增加，先前劃分的最內層Al2O3層以下有新的氧化物生成，顯示原先形成的不連續Al2O3層失去其保護性。另外，與預長氧化層處理之試片在相同環境下腐蝕的實驗結果比較，歸納出以下結果：在高溫空氣環境中形成的連續Al2O3層，在8.3 ppm 、700℃超臨界水環境中，依舊保持其完整性，經長時間腐蝕之後仍能發揮保護效果。

摘要 i
Abstract iii
誌謝 v
目錄 vii
表目錄 ix
圖目錄 x

第一章 前言與研究動機 1

第二章 文獻回顧 5
2.1 超臨界水核反應器之發展進程 5
2.2 超臨界水之特性 7
2.3 金屬材料於超臨界水環境下之腐蝕行為 8
2.3.1肥粒麻田鐵 (Ferritic-martensitic steel) 8
2.3.2氧化物散布強化鋼 (Oxide dispersion strengthened (ODS) steel) 9
2.3.3奧斯田不銹鋼 (Austenitic stainless steel) 11
2.3.4可形成氧化鋁層不鏽鋼 (Alumina-forming austenitic (AFA) stainless steel) 12
2.3.5鎳基超合金 (Ni-base superalloy) 13
2.4 鎳基超合金的發展與應用 15

第三章 實驗原理與方法 43
3.1 腐蝕實驗 43
3.1.1合金試片製備 43
3.1.2超臨界水循環系統 43
3.2 實驗分析方法 45
3.2.1電子顯微鏡原理 45
3.2.2電子束與物質之交互作用 46
3.2.3穿透式電子顯微鏡系統(TEM) 47
3.2.4電子槍 47
3.2.5能量散布能譜儀(EDS) 49
3.2.6穿透式電子顯微鏡(TEM)試片製備 50
3.2.7掠角X光繞射分析儀(GIXRD) 51

第四章 結果與討論 59
4.1 腐蝕動力學 59
4.2 氧化層分析 60
4.2.1 表面分析 60
4.2.2 TEM橫截面分析 61
4.2.3 GIXRD繞射分析 63
4.3腐蝕機制 64
4.3.1氧化層結構變化 64
4.3.2氧化層厚度變化 67
4.3.3 Al2O3層之連續性對抗腐蝕能力的影響 67
4.4析出相之微結構分析 68

第五章 結論 96

第六章 未來研究方向 98

參考文獻 99

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